• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.857-863
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• 1998

배관내에서 서로 다른 온도의 유체가 밀도차에 의해서 층이 분리된 채 존재하는 현상을 열성층 (thermal stratification) 현상이라 부르며, 이 현상에 의한 과도한 열응력은 배관의 건전성을 저해할 수 있다. 국내 원전의 경우 영광 3,4호기 이전의 밀림배관에서는 열성층 영향을 고려치 못하여 이에 대한 건전성 평가가 요구되고 있다. 본 연구에서는 고리 4호기 가압기 밀림배관을 대상으로 밀림배관내 유동해석 및 발전소 전 운전조건에 대하여 밀림배관 단면 온도분포 실측실험을 통하여 열성층화 현상의 발생 정도를 확인 하였으며 실측 온도 데이터를 이용하여 열응력해석 등을 수행함으로써 밀림배관의 열성층 영향을 평가한 결과 건전함이 확인되었다.

• Journal of Energy Engineering
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• v.6 no.2
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• pp.119-128
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• 1997

A method to mitigate the thermal stratification flow of a horizontal pipe line is proposed by heating external bottom of the pipe with electrical heat tracing. Unsteady two dimensional model has been used to numerically investigate an effect of the external heating on the thermal stratification flow. The dimensionless governing equations are solved by using the control volume formulation and SIMPLE algorithm. Temperature distribution, streamline profile and Nusselt number distributions are analyzed under heating conditions. The numerical results of this study show that the maximum dimensionless temperature difference between hot and cold sections of the inner wall of pipe is 0.424 at dimensionless time of 1,500 and the thermal stratification phenomenon disappears at about dimensionless time of 9,000.

• Solar Energy
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• v.14 no.2
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• pp.3-16
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• 1994

The major objectives of the study are to suggest the optimal basic design conditions for the horizontal storage tank system. For this purspose computer simulation has been carried out to find the characteristics of flow patterns in horizontal storage tank, and experiments have been carried out for the duration of one turnover, Experimental parameters are volume flow rate(1 LPM to 4 LPM), amount of heat generated from heat sources(0 W to 100 W), and inlet and outlet port types of the storage tank(DD type, DO type, ID type, IO type).

• Proceedings of the KIEE Conference
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• 2000.07d
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• pp.2501-2503
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• 2000

본 연구는 윈자력발전소 원자로 냉각재 계통의 가압기 밀림배관내에서 서로 다른 온도의 유체가 밀도차에 의해 분리된 채 존재하는 열성층의 온도를 감시할 수 있는 시스템을 개발한다. 개발된 온도 감시 시스템은 국내원자력발전소 중 가장 오래된 고리원자력발전소 1호기의 수명연장과 관련하여 가압기 밀림배관의 열성층 온도를 측정하므로써 열성층화에 따른 배관의 건정성 여부를 평가하는데 사용한다.

• Nuclear Engineering and Technology
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• v.28 no.1
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• pp.27-35
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• 1996

In this paper, an unsteady analytical model for the thermal stratification in the pressurizer surge line of PWR plant has been proposed to investigate the temperature profile, flow characteristics, and thermal stress in the pipe. In this model, the interface level, between hot and cold fluid, is assumed to be a function of time while the other models had developed for time independent or steady state. The dimensionless governing equations are solved by using a SIMPLE (Semi-Implicit Method for Pressure Linked Equations) algorithm. The analysis result for an example shows that the maximum dimensionless temperature difference is about 0.78 between hot and cold sections of pipe wall and the maximum thermal stress by thermal stratification is calculated about 276 MPa at the dimensionless time 27.0 under given conditions.

• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.120-120
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• 1999

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.12 no.2
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• pp.25-33
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• 2016

The thermal stratification phenomenon in the nuclear power plant can cause abnormal deformation of the piping, contact with the support, damage to the support system. Repetition of the thermal stratification phenomenon or variation of the thermal boundary layer can cause thermal fatigue. Thermal stratification phenomenon in nuclear power plants is still an ongoing issue and active research has been carried out. In this paper, the current situation in Korean nuclear power plants is described, followed by the status of research and the future problems on the thermal stratification phenomenon in Korea.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.14 no.6
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• pp.503-511
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• 2002

Heat flow characteristics during hot water extraction process was studied experimentally. Data were taken at various outlet port type for the fixed inlet port type, inlet-outlet temperature differences and mass flow rates. In this study, the temperature distribution in a storage tank and an outlet temperature were measured to predict a degree of stratification in the storage tank, and a useful rate of hot water was analysed with respect to the variables dominating a extraction process. Experimental results show that the degree of stratification and useful rate of hot water are all high in a low flow rate in case of using modified distributor I (MDI) as the outlet port type.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.18 no.7
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• pp.603-611
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• 2006

A variety of schemes were sought for a mitigation of thermal stratification phenomenon in the branch piping of domestic nuclear power plant. Several mechanisms of thermal stratification occurrence were introduced in this paper. A number of factors were selected to find out the schemes for thermal stratification mitigation and the computational analysis were performed. The length of vertical branch piping, the diameter, the radius of curvature of the elbow, the direction of connection between main piping and branch piping, the slope of branch piping, the leakage flow rate, the installation of additional valve, the change of the 1st valve position and another branch piping connected with branch piping were mentioned as factors in this paper.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.18 no.3
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• pp.202-210
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• 2006

In the nuclear power plant, emergency core coolant system (ECCS) is furnished at reactor coolant system (RCS) in order to cool down high temperature water in case of emergency. However, in this coolant system, thermal stratification phenomenon can be occurred due to coolant leaking in the check valve. The thermal stratification produces excessive thormal stresses at the pipe wall so as to yield thermal fatigue crack (TFC) accident. In the present study, when the turbulence penetration occurs in the branch pipe, the maximum temperature differences of fluid at the pipe cross-sections of the T-branch with thermal stratification are examine.